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The impact of americium on transients in the European Lead-cooled SYstem ELSY loaded with nitride fuel
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.ORCID iD: 0000-0002-6082-8913
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.ORCID iD: 0000-0001-6818-5724
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
2012 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 50, 56-62 p.Article in journal (Refereed) Published
Abstract [en]

The Unprotected Loss-of-Flow transient (ULOF) and the Unprotected Transient-Over-Power (UTOP) have been evaluated for a modified design of the European Lead-cooled SYstem (ELSY) using nitride fuel. Additional americium has been added to the core in concentrations of 0%, 4% and 8%. During ULOF, fuel and clad asymptotic temperatures stabilize below limits. For UTOP, however, the maximum allowed cladding temperature limit is exceeded at EOC and introduction of a power penalty is necessary for Am transmutation. The power penalty is higher than that reported for SFR.

Place, publisher, year, edition, pages
2012. Vol. 50, 56-62 p.
Keyword [en]
ELSY; UTOP; ULOF; Nitride
National Category
Other Physics Topics
Identifiers
URN: urn:nbn:se:kth:diva-100196DOI: 10.1016/j.anucene.2012.07.007ISI: 000312120600008Scopus ID: 2-s2.0-84866522334OAI: oai:DiVA.org:kth-100196DiVA: diva2:542974
Note

QC 20130118. Updated from submitted to published.

Available from: 2012-08-06 Created: 2012-08-06 Last updated: 2017-12-07Bibliographically approved
In thesis
1. Science and Technology for Americium Transmutation
Open this publication in new window or tab >>Science and Technology for Americium Transmutation
2012 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

Americium could be seen as the most troublesome element that is presentin nuclear fuel. This thesis offers different points of view on the possibility ofamericium transmutation. The first point of view elaborates simulations ofamericium-bearing facilities, namely nuclear data, a popular computationalcode and modeling techniques. The second point of view is focused on practicalusage of the simulations to examine upper limit of americium in a specificreactor.

Abstract [sv]

Americium är ett av det mest besvärande elementen i använt kärnbränsle.Denna avhandling behandlar olika aspekter av möjligheten att transmuteraamericium i snabba reaktorsystem. I den första varianten utarbetas simuleringaroch beräkningsmodeller för neutrondatamätningar av betydelse föracceleratordrivna system avsedda att transmutera americium. I den senareundersöks mer praktiska tillämpningar, i synnerhet beräknas gränser för hurmycket americium som kan laddas i bränslet för kritiska bykylda reaktorer.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2012. xii, 62 p.
Series
TRITA-FYS, ISSN 0280-316X ; 2012:21
National Category
Other Physics Topics
Identifiers
urn:nbn:se:kth:diva-100186 (URN)978-91-7501-326-8 (ISBN)
Public defence
2012-08-17, F3, Lindstedtsvägen 26, KTH, Stockholm, 13:00 (English)
Opponent
Supervisors
Note

QC 20120806

Available from: 2012-08-06 Created: 2012-08-06 Last updated: 2017-03-02Bibliographically approved

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Wallenius, JanneJolkkonen, Mikael

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